• DocumentCode
    1454696
  • Title

    Long-Term Operation and Basic Corrosion Test in an Experimental Loop for Liquid Breeder in Korea

  • Author

    Yoon, Jae Sung ; Kim, Suk-Kwon ; Jung, Yang Il ; Lee, Dong Won ; Cho, Seungyon

  • Author_Institution
    Korea Atomic Energy Res. Inst., Daejeon, South Korea
  • Volume
    40
  • Issue
    3
  • fYear
    2012
  • fDate
    3/1/2012 12:00:00 AM
  • Firstpage
    777
  • Lastpage
    781
  • Abstract
    Korea has developed a liquid breeder blanket and participated in the test blanket module (TBM) program within the international thermonuclear experimental reactor group with a helium-cooled molten lithium (Li) concept. Based on this concept, helium and liquid Li were used as a coolant and breeder, respectively. Additionally, ferritic-martensitic steel (FMS) was considered as a structural material. However, according to our strategy for developing a liquid breeder TBM and its more relevant DEMO concept, not only liquid Li breeders, but also lead-Li (PbLi) breeders were considered. An experimental loop for a liquid breeder (ELLI) was constructed for the purpose of validating the design and fabrication of our electromagnetic (EM) pump; testing the effects of the magneto-hydro-dynamics; and investigating the compatibility of PbLi using structural materials such as FMS. In the ELLI, Pb-15.7Li, where Li is 15.7 at % (called PbLi hereafter), is used as the breeding material, and the EM pump circulates it through the loop. The maximum operating pressure and temperature in the loop are 0.5 MPa and 550 °C, respectively. In this paper, performance tests with the EM pump were carried out. During the three separate experiments, the EM pump was operated for 250 h with a speed of 0.16 m/s for corrosion tests. For a material of corrosion test, tubular-type specimens and cylindrical-type specimens were fabricated and installed in three test pots of the loop. After installing the specimens into the loop, the corrosion test was performed while the EM pump was operating with a 0.16 m/s flow rate at 340 °C for 250 h.
  • Keywords
    Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactor fuel; plasma toroidal confinement; DEMO concept; Korea; basic corrosion test; cylindrical-type specimens; electromagnetic pump; ferritic-martensitic steel; helium-cooled molten lithium; international thermonuclear experimental reactor group; lead-Li breeders; liquid Li breeders; liquid breeder blanket; long-term operation; loop test pots; magneto-hydro-dynamic effects; maximum operating pressure; maximum operating temperature; pressure 0.5 MPa; structural material; temperature 550 degC; test blanket module program; Corrosion; Fusion reactors; Inductors; Lithium; Magnetic liquids; Steel; Corrosion; electromagnetic (EM) pump; international thermonuclear experimental reactor (ITER); liquid breeder; test blanket module (TBM);
  • fLanguage
    English
  • Journal_Title
    Plasma Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0093-3813
  • Type

    jour

  • DOI
    10.1109/TPS.2012.2184775
  • Filename
    6156462